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Impact of divertor geometry on radiative divertor performance in JET H-mode plasmas

A E Jaervinen, S Brezinsek, C Giroud, M Groth, C Guillemaut, P Belo, M Brix, G Corrigan, P Drewelow, D Harting2016年Plasma Physics and Controlled FusionIF 2.2出版社

Radiative divertor operation in JET high confinement mode plasmas with the ITER-like wall has been experimentally investigated and simulated with EDGE2D-EIRENE in horizontal and vertical low field side (LFS) divertor configurations. The simulations show that the LFS divertor heat fluxes are reduced with N2-injection in similar fashion in both configurations, qualitatively consistent with experimental observations. The simulations show no substantial difference between the two configurations in the reduction of the peak LFS heat flux as a function of divertor radiation, nitrogen concentration, or pedestal Zeff. Consistently, experiments show similar divertor radiation and nitrogen injection levels for similar LFS peak heat flux reduction in both configurations. Nevertheless, the LFS strike point is predicted to detach at 20% lower separatrix density in the vertical than in the horizontal configuration. However, since the peak LFS heat flux in partial detachment in the vertical configurations is shifted towards the far scrape-off layer (SOL), the simulations predict no benefit in the reduction of LFS peak heat flux for a given upstream density in the vertical configuration relative to a horizontal one. A factor of 2 reduction of deuterium ionization source inside the separatrix is observed in the simulations when changing to the vertical configuration. The simulations capture the experimentally observed particle and heat flux reduction at the LFS divertor plate in both configurations, when adjusting the impurity injection rate to reproduce the measured divertor radiation. However, the divertor Dα-emissions are underestimated by a factor of 2–5, indicating a short-fall in radiation by the fuel species. In the vertical configuration, detachment is experimentally measured and predicted to start next to the strike point, extending towards the far SOL with increasing degree of detachment. In contrast, in the horizontal configuration, the entire divertor particle flux profile is reduced uniformly with increasing degree of detachment.

日本語訳

JET高约束模式等离子体中,具有ITER类似壁的辐射偏滤器运行已在水平与垂直低场侧(LFS)偏滤器构型中通过实验研究,并利用EDGE2D-EIRENE进行了模拟。模拟表明,在两种构型中,注入N₂均以相似方式降低LFS偏滤器热通量,这与实验观测定性一致。模拟显示,在偏滤器辐射、氮浓度或台基区有效电荷数(Zeff)的函数关系中,两种构型对LFS峰值热通量的降低没有显著差异。实验同样表明,在相似的LFS峰值热通量降低条件下,两种构型的偏滤器辐射和氮注入水平相近。然而,模拟预测,在垂直构型中,LFS打击点解贴所需的分离面密度比水平构型低20%。但鉴于在垂直构型的部分解贴状态下,LFS峰值热通量向远刮削层(SOL)偏移,模拟预测在给定上游密度下,垂直构型相对于水平构型在降低LFS峰值热通量方面并无优势。模拟中观察到,切换至垂直构型时,分离面内部的氘电离源减少为原来的二分之一。通过调整杂质注入速率以复现实测偏滤器辐射,模拟捕捉到了两种构型中实验观测到的粒子与热通量降低。然而,偏滤器Dα辐射被低估了2–5倍,表明燃料粒子辐射存在不足。在垂直构型中,解贴起始于打击点附近,并随解贴程度增加向远SOL延伸,这与实验测量和模拟预测一致。相比之下,在水平构型中,整个偏滤器粒子通量剖面随解贴程度增加而均匀降低。

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